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Proceedings Papers

Experimental Study on Transient Heat Transfer for Helium Gas Flowing in a Minichannel

Feng Xu, Qiusheng Liu, Satoshi Kawaguchi, Makoto Shibahara

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A039, August 4–5, 2020

Paper No: ICONE2020-16697

DOI: https://doi.org/10.1115/ICONE2020-16697

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Topics: Helium, Transient heat transfer, Heat, Flow (Dynamics), Temperature, Heat flux, Heat transfer coefficients, Transients (Dynamics), Control systems, Flowmeters

Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020

Paper No: ICONE2020-16897

DOI: https://doi.org/10.1115/ICONE2020-16897

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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations

Proceedings Papers

Uranium Enrichment Measurement Using Enrichment-Meter Approach

K. Abd El Gawad, Yushou Song

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A039, July 22–26, 2018

Paper No: ICONE26-82101

DOI: https://doi.org/10.1115/ICONE26-82101

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Topics: Uranium, Containers, Simulation, Accuracy and precision, Wall thickness, Calibration, Dimensions, Equilibrium (Physics), Gamma ray spectrometry, Germanium

Proceedings Papers

Analytical Study of Supercritical Water Flow in Two Heated Parallel Channels With Wall Heat Effects

Dhanashree S. Ghadge, Vijay Chatoorgoon

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A016, July 22–26, 2018

Paper No: ICONE26-81150

DOI: https://doi.org/10.1115/ICONE26-81150

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Topics: Flow (Dynamics), Heat, Water, Heat storage, Stability, Computer simulation, Wall thickness

Proceedings Papers

Study on Load Capacity of Main Steam Superpipe Nozzle Used in Nuclear Power Plant

Zhou Gengyu, Liang Shuhua, Sun Lin, Lv Feng

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A075, July 2–6, 2017

Paper No: ICONE25-66965

DOI: https://doi.org/10.1115/ICONE25-66965

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Topics: Nozzles, Nuclear power stations, Steam, Stress, Pipes, Finite element analysis, Safety, Computational methods, Design, Extruding

Proceedings Papers

Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project

Huadong Zhu

Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A011, July 2–6, 2017

Paper No: ICONE25-66339

DOI: https://doi.org/10.1115/ICONE25-66339

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Topics: Nuclear power, Surges, Wall thickness, Design, Pipes, Nuclear reactor coolants, Pressure, Engineering drawings, Fittings, Heating

Proceedings Papers

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

Huadong Zhu

Paper No: ICONE25-66026

DOI: https://doi.org/10.1115/ICONE25-66026

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Topics: Wall thickness, Design, In-service inspection, Inspection, Nuclear power, Nuclear power stations, Nuclear reactor coolants, Reactor vessels, Welded joints, Boilers

Proceedings Papers

Guided Waves As an Online Monitoring Technology for Long Term Operation in NPPs: New Experimental Results on a Steam Discharge Pipe

Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi

Paper No: ICONE25-67444

DOI: https://doi.org/10.1115/ICONE25-67444

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Topics: Nuclear power stations, Pipes, Steam, Waves, Probes, Sensors, Testing, Circuits, Echoes, Engineering simulation

Proceedings Papers

The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel

Ge Liang, Xu Xuguang, Cai Jiafan, Cheng Zhaoyu

Paper No: ICONE25-66984

DOI: https://doi.org/10.1115/ICONE25-66984

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Topics: Reactor vessels, Ultrasonic testing, Probes, Inspection, Alloys, Nuclear power stations, Accuracy and precision, Circuits, Corrosion, Design

Proceedings Papers

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

Zhou Lifeng, Cheng Zhaoyu, Cai Jiafan, Tang Yi

Paper No: ICONE25-66999

DOI: https://doi.org/10.1115/ICONE25-66999

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Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water

Proceedings Papers

Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube

Mark A. Brown, Hung Nguyen, Shripad T. Revankar, Jovica Riznic

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A046, July 2–6, 2017

Paper No: ICONE25-67371

DOI: https://doi.org/10.1115/ICONE25-67371

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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Nuclear power stations, Coolants, Accidents, Hydraulics, Leakage, Leak-before-break

Proceedings Papers

Non-Invasive On-Line Monitoring for Nuclear Power Plants Using Guided Waves Propagating in Steel Pipes With Different Types of Structural Complexity

Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi

Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T01A010, June 26–30, 2016

Paper No: ICONE24-60885

DOI: https://doi.org/10.1115/ICONE24-60885

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Topics: Nuclear power stations, Pipes, Steel, Waves, Failure, In-service inspection, Inspection, Life extension, Radiation (Physics), Robustness

Proceedings Papers

Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression

Chunzhen Yang, Jingquan Liu, Yuyun Zeng, Muhammad Saeed

Paper No: ICONE24-61114

DOI: https://doi.org/10.1115/ICONE24-61114

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Topics: Support vector machines, Uncertainty, Modeling, Nuclear power stations, Algorithms, Carbon steel, In-service inspection, Maintenance, Pipes, Sampling methods

Proceedings Papers

Experimental Investigation of Subcooled Choking Flow in a Steam Generator Tube Crack

Hung Nguyen, Mark Brown, Shripad T. Revankar, Jovica Riznic

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A017, June 26–30, 2016

Paper No: ICONE24-60309

DOI: https://doi.org/10.1115/ICONE24-60309

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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Coolants, Design, Nuclear power stations, Pressurized water reactors, Rupture, Water

Proceedings Papers

Outline of Specification for Composite SC Walls in Nuclear Facilities

Saahastaranshu R. Bhardwaj, Amit H. Varma, Taha Al-Shawaf

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A009, June 26–30, 2016

Paper No: ICONE24-60960

DOI: https://doi.org/10.1115/ICONE24-60960

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Topics: Composite materials, Nuclear power stations, Design, Shear (Mechanics), Steel, Failure, Safety, Accidents, Anchorage, Bending (Stress)

Proceedings Papers

Evaluation of Safety Performances of a Superficial Disposal Facility Subject to an Aircraft Impact and Fuel Burning

Lorenzo Stefanini, Rosa Lo Frano, Fulvio Bertocchi, Giuseppe Forasassi

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A067, July 7–11, 2014

Paper No: ICONE22-31188

DOI: https://doi.org/10.1115/ICONE22-31188

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Topics: Aircraft, Combustion, Fuels, Safety, Concretes, Boundary-value problems, Computer simulation, Design, Fire, Nuclear power stations

Proceedings Papers

Fretting Wear of the Zr Fuel Rod Cladding

Ladislav Pecinka, Jaroslav Svoboda, Vladimír Zeman

Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A027, July 7–11, 2014

Paper No: ICONE22-31103

DOI: https://doi.org/10.1115/ICONE22-31103

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Topics: Cladding systems (Building), Fuel rods, Wear, Zirconium, Fuels, Nuclear power stations, Pressurized water reactors, Damage, Failure, Flow (Dynamics)

Proceedings Papers

A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld

Seung-gun Lee, Youngho Son

Paper No: ICONE22-31083

DOI: https://doi.org/10.1115/ICONE22-31083

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Topics: Heat treating (Metalworking), Relaxation (Physics), Stress, Finite element analysis, Heat, Alloy steel, Engineering standards, Fracture (Materials), Furnaces, Nuclear power stations

Proceedings Papers

The Role of CHECWORKS™ in an Effective FAC Program

David Smith, Jeffrey Horowitz

Paper No: ICONE22-30854

DOI: https://doi.org/10.1115/ICONE22-30854

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Topics: Accidents, Carbon steel, Computer software, Condensed matter, Corrosion, Engineers, Failure, Flow (Dynamics), Fossil fuels, Inspection

Proceedings Papers

Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings

J. Jennifer Zhang, Lee J. Tunon-Sanjur

Paper No: ICONE22-31263

DOI: https://doi.org/10.1115/ICONE22-31263

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Topics: Accidents, Concrete cracking, Finite element model, Reinforced concrete, Computer simulation, Concretes, Design, Fracture (Materials), Stiffness, Structural design

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NARROW

Experimental Study on Transient Heat Transfer for Helium Gas Flowing in a Minichannel

Probability of Rupture for WWER-1000 Main Piping

Uranium Enrichment Measurement Using Enrichment-Meter Approach

Analytical Study of Supercritical Water Flow in Two Heated Parallel Channels With Wall Heat Effects

Study on Load Capacity of Main Steam Superpipe Nozzle Used in Nuclear Power Plant

Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

Guided Waves As an Online Monitoring Technology for Long Term Operation in NPPs: New Experimental Results on a Steam Discharge Pipe

The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube

Non-Invasive On-Line Monitoring for Nuclear Power Plants Using Guided Waves Propagating in Steel Pipes With Different Types of Structural Complexity

Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression

Experimental Investigation of Subcooled Choking Flow in a Steam Generator Tube Crack

Outline of Specification for Composite SC Walls in Nuclear Facilities

Evaluation of Safety Performances of a Superficial Disposal Facility Subject to an Aircraft Impact and Fuel Burning

Fretting Wear of the Zr Fuel Rod Cladding

A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld

The Role of CHECWORKS™ in an Effective FAC Program

Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings

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